Refueling method, device, equipment, medium and product of nuclear power station unit

Abstract

The invention relates to a refueling method, device and equipment of a nuclear power station unit, a medium and a product. The method comprises the following steps: determining an initial unloading direction according to the arrangement position of a fuel transmission device in a nuclear power station unit; wherein at least one fuel assembly is arranged in a reactor core of the nuclear power station unit; selecting an initial unloading assembly from the at least one candidate fuel assembly; wherein the at least one candidate fuel assembly is at least one fuel assembly arranged in the initial discharging direction; and the fuel assemblies are sequentially unloaded according to a first preset route from the initial unloading assembly. And the method can adapt to a nuclear power station unit using an HPR unit.

Description

Technical Field

[0001] The present application relates to the technical field of nuclear power plant core installation, and in particular to a material replacement method, device, equipment, medium and product for a nuclear power plant unit. Background Art

[0002] At present, nuclear power plants generate electricity mainly by nuclear fission of fuel assemblies in the core of pressurized water reactors to generate a large amount of heat energy, which is then converted into electrical energy. As the use time increases, the reactive materials in the fuel assemblies will decrease until they are replaced.

[0003] Since there are hundreds of fuel assemblies in the core, it is more difficult to load and unload fuel for units with longer fuel assemblies. The current refueling method is usually based on the existing CPR units. However, since the characteristics of the fuel assemblies and source range probes loaded in the core of the HPR unit are quite different from those of the CPR unit, the existing refueling mode is not suitable for the core of the HPR unit. Summary of the invention

[0004] Based on this, it is necessary to provide a material replacement method, device, equipment, medium and product that can be adapted to nuclear power plant units using HPR units in response to the above technical problems.

[0005] In a first aspect, the present application provides a method for refueling a nuclear power plant unit, comprising:

[0006] Determine the starting unloading direction according to the setting position of the fuel transfer device in the nuclear power plant unit; wherein at least one fuel assembly is arranged in the core of the nuclear power plant unit;

[0007] Selecting a starting unloading assembly from at least one candidate fuel assembly; wherein the at least one candidate fuel assembly is at least one fuel assembly disposed in a starting unloading direction;

[0008] Starting from the initial unloading assembly, each fuel assembly is unloaded in sequence according to the first preset route.

[0009] In one embodiment, starting from the initial unloading assembly, unloading each fuel assembly in sequence according to a first preset route includes:

[0010] Starting from the initial unloading assembly, unloading each fuel assembly in the nuclear power plant unit according to a first preset route;

[0011] After the unloading of each fuel assembly is completed, for any neutron source assembly in the nuclear power plant unit, the neutron source assembly is switched from the corresponding initial position to the corresponding first target position.

[0012] In one embodiment, the first target position corresponding to the neutron source assembly is determined based on:

[0013] Obtain the switching reference angle of the nuclear power plant units;

[0014] Determining a first offset distance according to a switching reference angle and a core reference radius of a nuclear power plant unit;

[0015] A first target position corresponding to the neutron source assembly is determined according to the first offset distance and the initial position of the neutron source assembly.

[0016] In one embodiment, the method further comprises:

[0017] According to the setting position of the source range detector in the nuclear power plant unit, determine the temporary placement position of each neutron source component in the nuclear power plant unit;

[0018] Placing each neutron source assembly in a nuclear power plant unit at a corresponding temporary storage position;

[0019] Starting from the preset starting loading assembly, the fuel assemblies in the nuclear power plant units are loaded sequentially according to the second preset route.

[0020] In one embodiment, the method further comprises:

[0021] After the loading of each fuel assembly is completed, for any neutron source assembly, the neutron source assembly is switched from the corresponding temporary storage position to the corresponding second target position.

[0022] In one embodiment, the second target position corresponding to the neutron source assembly is determined based on:

[0023] Obtain the switching reference angle of the nuclear power plant units;

[0024] Determining a second offset distance according to a switching reference angle and a core reference radius of a nuclear power plant unit;

[0025] A second target position corresponding to the neutron source assembly is determined according to the second offset distance and the temporary placement position of the neutron source assembly.

[0026] In a second aspect, the present application also provides a refueling device for a nuclear power plant unit, comprising:

[0027] A first determination module is used to determine the starting unloading direction according to the setting position of the fuel transfer device in the nuclear power plant unit; wherein at least one fuel assembly is set in the core of the nuclear power plant unit;

[0028] A selection module, used to select a starting unloading assembly from at least one candidate fuel assembly; wherein the at least one candidate fuel assembly is at least one fuel assembly arranged in a starting unloading direction;

[0029] The unloading module is used to unload each fuel assembly in sequence according to a first preset route starting from the starting unloading assembly.

[0030] In a third aspect, the present application further provides a computer device, including a memory and a processor, wherein the memory stores a computer program, and when the processor executes the computer program, the following steps are implemented:

[0031] Determine the starting unloading direction according to the setting position of the fuel transfer device in the nuclear power plant unit; wherein at least one fuel assembly is arranged in the core of the nuclear power plant unit;

[0032] Selecting a starting unloading assembly from at least one candidate fuel assembly; wherein the at least one candidate fuel assembly is at least one fuel assembly disposed in a starting unloading direction;

[0033] Starting from the initial unloading assembly, each fuel assembly is unloaded in sequence according to the first preset route.

[0034] In a fourth aspect, the present application further provides a computer-readable storage medium having a computer program stored thereon, and when the computer program is executed by a processor, the following steps are implemented:

[0035] Determine the starting unloading direction according to the setting position of the fuel transfer device in the nuclear power plant unit; wherein at least one fuel assembly is arranged in the core of the nuclear power plant unit;

[0036] Selecting a starting unloading assembly from at least one candidate fuel assembly; wherein the at least one candidate fuel assembly is at least one fuel assembly disposed in a starting unloading direction;

[0037] Starting from the initial unloading assembly, each fuel assembly is unloaded in sequence according to the first preset route.

[0038] In a fifth aspect, the present application further provides a computer program product, including a computer program, which implements the following steps when executed by a processor:

[0039] Determine the starting unloading direction according to the setting position of the fuel transfer device in the nuclear power plant unit; wherein at least one fuel assembly is arranged in the core of the nuclear power plant unit;

[0040] Selecting a starting unloading assembly from at least one candidate fuel assembly; wherein the at least one candidate fuel assembly is at least one fuel assembly disposed in a starting unloading direction;

[0041] Starting from the initial unloading assembly, each fuel assembly is unloaded in sequence according to the first preset route.

[0042] The above-mentioned refueling method, device, equipment, medium and product of the nuclear power plant unit, when determining the starting unloading direction, takes into account the setting position of the fuel transfer device in the nuclear power plant unit, so that the walking path of the refueling machine during unloading is at the removed fuel assembly, which can effectively reduce the risk of fuel passing over the core. Further, the starting unloading assembly is selected from at least one fuel assembly set in the starting unloading direction, and starting from the starting unloading assembly, each fuel assembly is unloaded in sequence according to the planned first preset route, which can ensure that emergency situations can be safely responded to, and based on the first preset route, the risk of positioning errors can be reduced. BRIEF DESCRIPTION OF THE DRAWINGS

[0043] In order to more clearly illustrate the technical solutions in the embodiments of the present application or related technologies, the drawings required for use in the embodiments of the present application or related technical descriptions will be briefly introduced below. Obviously, the drawings described below are only some embodiments of the present application. For ordinary technicians in this field, other related drawings can be obtained based on these drawings without paying creative work.

[0044] Figure 1 A schematic flow chart of a method for refueling a nuclear power plant unit in one embodiment;

[0045] Figure 2 A schematic flow diagram of a discharging step in one embodiment;

[0046] Figure 3 A schematic flow diagram of a charging step in one embodiment;

[0047] Figure 4A A schematic flow chart of a material replacement method for a nuclear power plant unit in another embodiment;

[0048] Figure 4B A schematic flow chart of the first loading step in one embodiment;

[0049] Figure 4C A schematic diagram of a nuclear power plant unit in one embodiment;

[0050] Figure 4D A schematic flow chart of a discharging step in another embodiment;

[0051] Figure 4E A schematic diagram of a nuclear power plant unit in another embodiment;

[0052] Figure 4F A schematic flow diagram of a charging step in another embodiment;

[0053] Figure 4G A schematic diagram of a nuclear power plant unit in another embodiment;

[0054] Figure 5is a structural block diagram of a material replacement device for a nuclear power plant unit in one embodiment;

[0055] Figure 6 FIG. 4 is a diagram showing the internal structure of a computer device in one embodiment. DETAILED DESCRIPTION

[0056] In order to make the purpose, technical solution and advantages of the present application more clearly understood, the present application is further described in detail below in conjunction with the accompanying drawings and embodiments. It should be understood that the specific embodiments described herein are only used to explain the present application and are not used to limit the present application.

[0057] In one embodiment, Figure 1 As shown, a method for refueling a nuclear power plant unit is provided. This embodiment uses the method applied to a terminal as an example for illustration. It can be understood that the method can also be applied to a server, and can also be applied to a system including a terminal and a server, and is implemented through the interaction between the terminal and the server. In this embodiment, the method includes the following steps:

[0058] S110, determining a starting unloading direction according to a setting position of a fuel transfer device in a nuclear power plant unit.

[0059] The nuclear power plant unit may be any type of unit, and the nuclear power plant unit in this embodiment mainly refers to the HPR unit. At least one fuel assembly is arranged in the core of the nuclear power plant unit.

[0060] It should be noted that the HPR unit has 177 fuel assemblies loaded in the core, with an assembly length of 4060 mm; there are three RPN source range probes in the core, and the core position layout of the source range probes is different from that of the CPR unit. The number of assemblies and the characteristics of the source range probes determine that the HPR unit has a different refueling mode compared with other units (CPR, EPR). Therefore, previous mature experience is not applicable to the HPR unit.

[0061] For example, in this embodiment, the location of the fuel transfer device can be used as the starting unloading direction. If the fuel transfer device is set at 90 degrees, the 90-degree direction of the core is used as the starting unloading direction; if the fuel transfer device is set at 180 degrees, the 180-degree direction of the core is used as the starting unloading direction.

[0062] S120, selecting a starting unloading assembly from at least one candidate fuel assembly.

[0063] Among them, at least one candidate fuel assembly is at least one fuel assembly arranged in the starting unloading direction. In this embodiment, the candidate fuel assemblies can be the fuel assemblies arranged in the starting unloading direction and at the edge of the core.

[0064] Illustratively, in this embodiment, any one of at least one candidate fuel assembly may be selected as the starting unloading assembly, or one of at least one candidate fuel assembly may be selected as the starting unloading assembly according to a preset assembly selection rule.

[0065] For example, the at least one candidate fuel assembly at an edge position may be used as the starting unloading assembly.

[0066] S130, starting from the initial unloading assembly, unloading each fuel assembly in sequence according to the first preset route.

[0067] The first preset route may be determined based on manual experience or through a large number of experiments, and the present application does not impose any limitation on this. For example, the first preset route may be a parallel route.

[0068] Specifically, in this embodiment, starting from the initial unloading assembly, each fuel assembly is unloaded in sequence according to the first preset route until all fuel assemblies in the nuclear power plant unit are unloaded.

[0069] In the above-mentioned refueling method of a nuclear power plant unit, when determining the starting unloading direction, the setting position of the fuel transfer device in the nuclear power plant unit is taken into consideration, so that the walking path of the refueling machine during unloading is at the location of the removed fuel assembly, which can effectively reduce the risk of the fuel passing over the core. Furthermore, a starting unloading assembly is selected from at least one fuel assembly arranged in the starting unloading direction, and starting from the starting unloading assembly, each fuel assembly is unloaded in sequence according to the planned first preset route, which can ensure that an emergency situation can be safely responded to, and based on the first preset route, the risk of positioning errors can be reduced.

[0070] Based on the technical solutions of the above embodiments, the present application also provides an optional embodiment. In this optional embodiment, the process of unloading each fuel assembly in sequence from the initial unloading assembly according to the first preset route is refined.

[0071] See also Figure 2 The unloading steps shown include:

[0072] S210, starting from the initial unloading assembly, unloading each fuel assembly in the nuclear power plant unit according to a first preset route.

[0073] S220, after each fuel assembly is unloaded, for any neutron source assembly in the nuclear power plant unit, the neutron source assembly is switched from the corresponding initial position to the corresponding first target position.

[0074] Among them, the first target position corresponding to the neutron source assembly is determined according to the following method: obtaining the switching reference angle of the nuclear power plant unit; determining the first offset distance according to the switching reference angle and the core reference radius of the nuclear power plant unit; determining the first target position corresponding to the neutron source assembly according to the first offset distance and the initial position of the neutron source assembly.

[0075] The switching reference angle may be an angle used to determine the switching position. In this embodiment, the switching reference angle may be obtained based on a preset rule. For example, assuming that the core circle radius of the nuclear power plant unit is R and the side length of each fuel assembly square is n, the switching reference angle may be determined by the following formula:

[0076] ;

[0077] Accordingly, the first offset distance can be determined by the following formula:

[0078] ;

[0079] Where, L 1 is the first offset distance; θ is the switching reference angle; R is the core circle radius of the nuclear power plant unit.

[0080] In another optional implementation manner, the switching reference angle may also be determined by the following formula:

[0081] ;

[0082] Accordingly, the first offset distance can be determined by the following formula:

[0083] ;

[0084] Where, L 2 is the second first offset distance; g is the switching reference angle; R is the core circle radius of the nuclear power plant unit.

[0085] Based on the technical solutions of the above embodiments, the present application also provides an optional embodiment. In this optional embodiment, a loading step after unloading is provided to make the material changing process more complete.

[0086] See also Figure 3 The charging steps shown include:

[0087] S310, determining the temporary placement position of each neutron source assembly in the nuclear power plant unit according to the setting position of the source range detector in the nuclear power plant unit.

[0088] Exemplarily, in this embodiment, the temporary placement position of each neutron source assembly may be around each source range detector.

[0089] S320, placing each neutron source assembly in the nuclear power plant unit at a corresponding temporary storage position.

[0090] Specifically, in this embodiment, the neutron source assembly can be first loaded near each source range detector, and the loading position is consistent with the unloading switching position, which is conducive to obtaining a higher neutron count.

[0091] S330, starting from a preset starting loading assembly, the fuel assemblies in the nuclear power plant units are loaded sequentially according to a second preset route.

[0092] The preset starting loading assembly may be determined based on manual experience or through a large number of tests, and the present application does not impose any limitation on this. For example, the preset starting loading assembly may be the lower left corner of the core of a nuclear power plant unit.

[0093] The second preset route can be determined based on manual experience or through a large number of experiments, and the present application does not impose any limitation on this. The second preset route can be the same as the first preset route or different from the first preset route. Exemplarily, the second preset route can be a serpentine route for easy arrangement.

[0094] Furthermore, after the loading of each fuel assembly is completed, for any neutron source assembly, the neutron source assembly is switched from the corresponding temporary storage position to the corresponding second target position.

[0095] Among them, the second target position corresponding to the neutron source assembly is determined based on the following method: obtaining the switching reference angle of the nuclear power plant unit; determining the second offset distance according to the switching reference angle and the core reference radius of the nuclear power plant unit; determining the second target position corresponding to the neutron source assembly according to the second offset distance and the temporary placement position of the neutron source assembly.

[0096] The second offset distance may be determined in the same manner as the first offset distance, which will not be described in detail herein.

[0097] Based on the technical solutions of the above embodiments, the present application also provides an optional embodiment. In this optional embodiment, the material replacement method of the nuclear power plant unit provided by the present application is introduced in detail.

[0098] See also Figure 4A The refueling method of the nuclear power plant unit shown includes:

[0099] S410A, first charge;

[0100] S420A, overhaul unloading;

[0101] S430A, overhaul charge.

[0102] Further, see Figure 4BThe first loading steps shown in the figure are described in detail for the steps of S410A above, and include the following steps:

[0103] S410B, installation of additional temporary detectors in the core;

[0104] Among them, temporary detectors are used to monitor the number of neutrons;

[0105] S420B, before loading, setting the detector to have an assembly, using a fuel assembly with an activated secondary neutron source near the detector to check the detector availability;

[0106] S430B, loading according to U-type loading mode;

[0107] For example, see Figure 4C The nuclear power plant unit shown can start loading from the lower left corner of the core, and leave an emergency parking position for the core replacement machine to deal with emergencies.

[0108] Further, see Figure 4D The unloading steps shown in the figure are described in detail for the steps of S420A above, and include the following steps:

[0109] S410D, determining the starting unloading direction according to the setting position of the fuel transfer device in the nuclear power plant unit;

[0110] Wherein, at least one fuel assembly is arranged in the core of the nuclear power plant unit;

[0111] S420D, selecting a starting unloading assembly from at least one candidate fuel assembly;

[0112] wherein at least one candidate fuel assembly is at least one fuel assembly disposed in a starting unloading direction;

[0113] S430D, starting from the initial unloading assembly, unloading each fuel assembly in the nuclear power plant unit according to the first preset route;

[0114] S440D, after each fuel assembly is unloaded, for any neutron source assembly in the nuclear power plant unit, switching the neutron source assembly from the corresponding initial position to the corresponding first target position;

[0115] Among them, the first target position corresponding to the neutron source assembly is determined based on the following method: obtaining a switching reference angle of the nuclear power plant unit; determining a first offset distance based on the switching reference angle and the core reference radius of the nuclear power plant unit; determining the first target position corresponding to the neutron source assembly based on the first offset distance and the initial position of the neutron source assembly.

[0116] For example, see Figure 4EThe nuclear power plant unit shown can start unloading from the 90° direction of the core. During unloading, the path of the refueling machine is at the removed fuel assembly, which can effectively reduce the risk of fuel passing over the core; the starting position of unloading is the safe parking position of the refueling machine, and the first 4 steps of unloading are the emergency storage area of ​​the core (near R06), where the fuel assembly is first unloaded to safely respond to emergencies. After unloading is completed in the direction of the three source range channels, the neutron source assembly is switched in the pile, and the switching positions (i.e., the first target positions) are K01, M14, and A06.

[0117] It should be noted that during the unloading process, all the non-offset unloading steps with 3-surface contact ensure that there is no interference on the free surface, so that horizontal offset adjustment can be performed safely when the positioning grid interference and friction force are too large.

[0118] In addition, unloading along parallel routes is simple and easy to remember, friendly to the operator's operating habits, and helps reduce the risk of positioning errors.

[0119] Further, see Figure 4F The loading steps shown in the figure are described in detail for the steps of S430A above, and include the following steps:

[0120] S410F, determining the temporary placement position of each neutron source assembly in the nuclear power plant unit according to the setting position of the source range detector in the nuclear power plant unit;

[0121] S420F, placing each neutron source assembly in the nuclear power plant unit at a corresponding temporary storage position;

[0122] S430F, starting from a preset starting loading assembly, sequentially loading the fuel assemblies in the nuclear power plant units according to a second preset route;

[0123] S440F, after the loading of each fuel assembly is completed, for any neutron source assembly, the neutron source assembly is switched from the corresponding temporary storage position to the corresponding second target position;

[0124] Among them, the second target position corresponding to the neutron source assembly is determined based on the following method: obtaining the switching reference angle of the nuclear power plant unit; determining the second offset distance according to the switching reference angle and the core reference radius of the nuclear power plant unit; determining the second target position corresponding to the neutron source assembly according to the second offset distance and the temporary placement position of the neutron source assembly.

[0125] For example, see Figure 4GFor the nuclear power plant unit shown, first, the neutron source assembly is loaded near the three source range detectors (the loading position is consistent with the unloading and reversing position, which is conducive to obtaining a higher neutron count); secondly, in order to reserve an emergency parking position for the core refueling machine, the area near N03 is loaded last, starting from the lower left corner. Furthermore, the neutron source assembly is reversed within the pile, and the reversing positions are K01, M14, and A06, which is conducive to avoiding abnormal fluctuations in the core neutron count, abnormal adjustment of the 3θ value, and other operational risks.

[0126] In addition, the overall serpentine loading mode is adopted for easy arrangement, and the loading method of "first the two sides and then the middle" is adopted to avoid the situation where the components are "corner to diagonal (two fuel components are diagonally opposite without three-sided support)" and reduce the risk of component tipping.

[0127] It should be understood that, although the various steps in the flowcharts involved in the above-mentioned embodiments are displayed in sequence according to the indication of the arrows, these steps are not necessarily executed in sequence according to the order indicated by the arrows. Unless there is a clear explanation in this article, the execution of these steps does not have a strict order restriction, and these steps can be executed in other orders. Moreover, at least a part of the steps in the flowcharts involved in the above-mentioned embodiments can include multiple steps or multiple stages, and these steps or stages are not necessarily executed at the same time, but can be executed at different times, and the execution order of these steps or stages is not necessarily to be carried out in sequence, but can be executed in turn or alternately with other steps or at least a part of the steps or stages in other steps.

[0128] Based on the same inventive concept, the embodiment of the present application also provides a refueling device for a nuclear power plant unit for implementing the refueling method for a nuclear power plant unit involved above. The implementation scheme for solving the problem provided by the device is similar to the implementation scheme recorded in the above method, so the specific limitations in the embodiments of the refueling device for one or more nuclear power plant units provided below can refer to the limitations of the refueling method for a nuclear power plant unit above, and will not be repeated here.

[0129] In an exemplary embodiment, Figure 5 As shown, a material replacement device for a nuclear power plant unit is provided, comprising: a first determination module 510, a selection module 520 and a discharge module 530, wherein:

[0130] The first determination module 510 is used to determine the starting unloading direction according to the setting position of the fuel transfer device in the nuclear power plant unit; wherein at least one fuel assembly is set in the core of the nuclear power plant unit;

[0131] A selection module 520 is used to select a starting unloading assembly from at least one candidate fuel assembly; wherein the at least one candidate fuel assembly is at least one fuel assembly arranged in a starting unloading direction;

[0132] The unloading module 530 is used to unload each fuel assembly in sequence according to a first preset route starting from the initial unloading assembly.

[0133] In one embodiment, the unloading module 530 includes an unloading unit, which is used to unload each fuel assembly in the nuclear power plant unit according to a first preset route starting from a starting unloading assembly; and a switching unit, which is used to switch the neutron source assembly from the corresponding initial position to the corresponding first target position for any neutron source assembly in the nuclear power plant unit after the unloading of each fuel assembly is completed.

[0134] Among them, the first target position corresponding to the neutron source assembly is determined based on the following method: obtaining a switching reference angle of the nuclear power plant unit; determining a first offset distance based on the switching reference angle and the core reference radius of the nuclear power plant unit; determining the first target position corresponding to the neutron source assembly based on the first offset distance and the initial position of the neutron source assembly.

[0135] In one embodiment, the material replacement device of a nuclear power plant unit also includes a second determination module, which is used to determine the temporary storage position of each neutron source component in the nuclear power plant unit according to the setting position of the source range detector in the nuclear power plant unit; a setting module, which is used to set each neutron source component in the nuclear power plant unit at a corresponding temporary storage position; and a loading module, which is used to start from a preset starting loading component and load the fuel assemblies in the nuclear power plant unit in sequence according to a second preset route.

[0136] In one embodiment, the refueling device of the nuclear power plant unit further includes a switching module for switching the neutron source assembly from the corresponding temporary storage position to the corresponding second target position for any neutron source assembly after the loading of each fuel assembly is completed.

[0137] The second target position corresponding to the neutron source assembly is determined based on the following method:

[0138] Obtain the switching reference angle of the nuclear power plant units;

[0139] Determining a second offset distance according to a switching reference angle and a core reference radius of a nuclear power plant unit;

[0140] A second target position corresponding to the neutron source assembly is determined according to the second offset distance and the temporary placement position of the neutron source assembly.

[0141] Each module in the refueling device of the above-mentioned nuclear power plant unit can be implemented in whole or in part by software, hardware and a combination thereof. Each of the above-mentioned modules can be embedded in or independent of a processor in a computer device in the form of hardware, or can be stored in a memory in a computer device in the form of software, so that the processor can call and execute the operations corresponding to each of the above modules.

[0142] In an exemplary embodiment, a computer device is provided. The computer device may be a terminal, and its internal structure diagram may be as shown in FIG. Figure 6 As shown. The computer device includes a processor, a memory, an input / output interface, a communication interface, a display unit and an input device. The processor, the memory and the input / output interface are connected through a system bus, and the communication interface, the display unit and the input device are connected to the system bus through the input / output interface. The processor of the computer device is used to provide computing and control capabilities. The memory of the computer device includes a non-volatile storage medium and an internal memory. The non-volatile storage medium stores an operating system and a computer program. The internal memory provides an environment for the operation of the operating system and the computer program in the non-volatile storage medium. The input / output interface of the computer device is used to exchange information between the processor and an external device. The communication interface of the computer device is used to communicate with an external terminal in a wired or wireless manner, and the wireless manner can be realized through WIFI, a mobile cellular network, near field communication (NFC) or other technologies. When the computer program is executed by the processor, a method for changing fuel for a nuclear power plant unit is realized. The display unit of the computer device is used to form a visually visible picture, which can be a display screen, a projection device or a virtual reality imaging device. The display screen can be a liquid crystal display screen or an electronic ink display screen, and the input device of the computer device can be a touch layer covering the display screen, or a button, trackball or touchpad set on the computer device shell, or an external keyboard, touchpad or mouse.

[0143] Those skilled in the art will understand that Figure 6 The structure shown in the figure is only a block diagram of a part of the structure related to the solution of the present application, and does not constitute a limitation on the computer device to which the solution of the present application is applied. The specific computer device may include more or fewer components than those shown in the figure, or combine certain components, or have a different arrangement of components.

[0144] In an exemplary embodiment, a computer device is provided, including a memory and a processor, wherein a computer program is stored in the memory, and when the processor executes the computer program, the following steps are implemented:

[0145] Determine the starting unloading direction according to the setting position of the fuel transfer device in the nuclear power plant unit; wherein at least one fuel assembly is arranged in the core of the nuclear power plant unit;

[0146] Selecting a starting unloading assembly from at least one candidate fuel assembly; wherein the at least one candidate fuel assembly is at least one fuel assembly disposed in a starting unloading direction;

[0147] Starting from the initial unloading assembly, each fuel assembly is unloaded in sequence according to the first preset route.

[0148] In one embodiment, when the processor executes the computer program, the processor further implements the following steps:

[0149] Starting from the initial unloading assembly, unloading each fuel assembly in the nuclear power plant unit according to a first preset route;

[0150] After the unloading of each fuel assembly is completed, for any neutron source assembly in the nuclear power plant unit, the neutron source assembly is switched from the corresponding initial position to the corresponding first target position.

[0151] In one embodiment, when the processor executes the computer program, the processor further implements the following steps:

[0152] Obtain the switching reference angle of the nuclear power plant units;

[0153] Determining a first offset distance according to a switching reference angle and a core reference radius of a nuclear power plant unit;

[0154] A first target position corresponding to the neutron source assembly is determined according to the first offset distance and the initial position of the neutron source assembly.

[0155] In one embodiment, when the processor executes the computer program, the processor further implements the following steps:

[0156] According to the setting position of the source range detector in the nuclear power plant unit, determine the temporary placement position of each neutron source component in the nuclear power plant unit;

[0157] Placing each neutron source assembly in a nuclear power plant unit at a corresponding temporary storage position;

[0158] Starting from the preset starting loading assembly, the fuel assemblies in the nuclear power plant units are loaded sequentially according to the second preset route.

[0159] In one embodiment, when the processor executes the computer program, the processor further implements the following steps:

[0160] After the loading of each fuel assembly is completed, for any neutron source assembly, the neutron source assembly is switched from the corresponding temporary storage position to the corresponding second target position.

[0161] In one embodiment, when the processor executes the computer program, the processor further implements the following steps:

[0162] Obtain the switching reference angle of the nuclear power plant units;

[0163] Determining a second offset distance according to a switching reference angle and a core reference radius of a nuclear power plant unit;

[0164] A second target position corresponding to the neutron source assembly is determined according to the second offset distance and the temporary placement position of the neutron source assembly.

[0165] In one embodiment, a computer readable storage medium is provided, on which a computer program is stored, and when the computer program is executed by a processor, the following steps are implemented:

[0166] Determine the starting unloading direction according to the setting position of the fuel transfer device in the nuclear power plant unit; wherein at least one fuel assembly is arranged in the core of the nuclear power plant unit;

[0167] Selecting a starting unloading assembly from at least one candidate fuel assembly; wherein the at least one candidate fuel assembly is at least one fuel assembly disposed in a starting unloading direction;

[0168] Starting from the initial unloading assembly, each fuel assembly is unloaded in sequence according to the first preset route.

[0169] In one embodiment, when the computer program is executed by a processor, the following steps are also implemented:

[0170] Starting from the initial unloading assembly, unloading each fuel assembly in the nuclear power plant unit according to a first preset route;

[0171] After the unloading of each fuel assembly is completed, for any neutron source assembly in the nuclear power plant unit, the neutron source assembly is switched from the corresponding initial position to the corresponding first target position.

[0172] In one embodiment, when the computer program is executed by a processor, the following steps are also implemented:

[0173] Obtain the switching reference angle of the nuclear power plant units;

[0174] Determining a first offset distance according to a switching reference angle and a core reference radius of a nuclear power plant unit;

[0175] A first target position corresponding to the neutron source assembly is determined according to the first offset distance and the initial position of the neutron source assembly.

[0176] In one embodiment, when the computer program is executed by a processor, the following steps are also implemented:

[0177] According to the setting position of the source range detector in the nuclear power plant unit, determine the temporary placement position of each neutron source component in the nuclear power plant unit;

[0178] Placing each neutron source assembly in a nuclear power plant unit at a corresponding temporary storage position;

[0179] Starting from the preset starting loading assembly, the fuel assemblies in the nuclear power plant units are loaded sequentially according to the second preset route.

[0180] In one embodiment, when the computer program is executed by a processor, the following steps are also implemented:

[0181] After the loading of each fuel assembly is completed, for any neutron source assembly, the neutron source assembly is switched from the corresponding temporary storage position to the corresponding second target position.

[0182] In one embodiment, when the computer program is executed by a processor, the following steps are also implemented:

[0183] Obtain the switching reference angle of the nuclear power plant units;

[0184] Determining a second offset distance according to a switching reference angle and a core reference radius of a nuclear power plant unit;

[0185] A second target position corresponding to the neutron source assembly is determined according to the second offset distance and the temporary placement position of the neutron source assembly.

[0186] In one embodiment, a computer program product is provided, comprising a computer program, which, when executed by a processor, implements the following steps:

[0187] Determine the starting unloading direction according to the setting position of the fuel transfer device in the nuclear power plant unit; wherein at least one fuel assembly is arranged in the core of the nuclear power plant unit;

[0188] Selecting a starting unloading assembly from at least one candidate fuel assembly; wherein the at least one candidate fuel assembly is at least one fuel assembly disposed in a starting unloading direction;

[0189] Starting from the initial unloading assembly, each fuel assembly is unloaded in sequence according to the first preset route.

[0190] In one embodiment, when the computer program is executed by a processor, the following steps are also implemented:

[0191] Starting from the initial unloading assembly, unloading each fuel assembly in the nuclear power plant unit according to a first preset route;

[0192] After the unloading of each fuel assembly is completed, for any neutron source assembly in the nuclear power plant unit, the neutron source assembly is switched from the corresponding initial position to the corresponding first target position.

[0193] In one embodiment, when the computer program is executed by a processor, the following steps are also implemented:

[0194] Obtain the switching reference angle of the nuclear power plant units;

[0195] Determining a first offset distance according to a switching reference angle and a core reference radius of a nuclear power plant unit;

[0196] A first target position corresponding to the neutron source assembly is determined according to the first offset distance and the initial position of the neutron source assembly.

[0197] In one embodiment, when the computer program is executed by a processor, the following steps are also implemented:

[0198] According to the setting position of the source range detector in the nuclear power plant unit, determine the temporary placement position of each neutron source component in the nuclear power plant unit;

[0199] Placing each neutron source assembly in a nuclear power plant unit at a corresponding temporary storage position;

[0200] Starting from the preset starting loading assembly, the fuel assemblies in the nuclear power plant units are loaded sequentially according to the second preset route.

[0201] In one embodiment, when the computer program is executed by a processor, the following steps are also implemented:

[0202] After the loading of each fuel assembly is completed, for any neutron source assembly, the neutron source assembly is switched from the corresponding temporary storage position to the corresponding second target position.

[0203] In one embodiment, when the computer program is executed by a processor, the following steps are also implemented:

[0204] Obtain the switching reference angle of the nuclear power plant units;

[0205] Determining a second offset distance according to a switching reference angle and a core reference radius of a nuclear power plant unit;

[0206] A second target position corresponding to the neutron source assembly is determined according to the second offset distance and the temporary placement position of the neutron source assembly.

[0207] Those skilled in the art can understand that all or part of the processes in the above-mentioned embodiments can be completed by instructing the relevant hardware through a computer program, and the computer program can be stored in a non-volatile computer-readable storage medium. When the computer program is executed, it can include the processes of the embodiments of the above-mentioned methods. Among them, any reference to the memory, database or other medium used in the embodiments provided in this application can include at least one of non-volatile memory and volatile memory. Non-volatile memory can include read-only memory (ROM), magnetic tape, floppy disk, flash memory, optical memory, high-density embedded non-volatile memory, resistive random access memory (ReRAM), magnetic random access memory (MRAM), ferroelectric random access memory (FRAM), phase change memory (PCM), graphene memory, etc. Volatile memory can include random access memory (RAM) or external cache memory, etc. As an illustration and not limitation, RAM can be in various forms, such as static random access memory (SRAM) or dynamic random access memory (DRAM). The database involved in each embodiment provided in this application may include at least one of a relational database and a non-relational database. Non-relational databases may include distributed databases based on blockchains, etc., but are not limited to this. The processor involved in each embodiment provided in this application may be a general-purpose processor, a central processing unit, a graphics processor, a digital signal processor, a programmable logic device, a data processing logic device based on quantum computing, an artificial intelligence (AI) processor, etc., but are not limited to this.

[0208] The technical features of the above embodiments may be combined arbitrarily. To make the description concise, not all possible combinations of the technical features in the above embodiments are described. However, as long as there is no contradiction in the combination of these technical features, they should be considered to be within the scope of this application.

[0209] The above embodiments only express several implementation methods of the present application, and the descriptions thereof are relatively specific and detailed, but they cannot be understood as limiting the scope of the present application. It should be pointed out that, for a person of ordinary skill in the art, several variations and improvements can be made without departing from the concept of the present application, and these all belong to the protection scope of the present application. Therefore, the protection scope of the present application shall be subject to the attached claims.

Claims

1. A method for refueling a nuclear power plant unit, characterized in that: The method comprises: Determining the starting unloading direction according to the setting position of the fuel transfer device in the nuclear power plant unit; wherein at least one fuel assembly is arranged in the core of the nuclear power plant unit; Selecting a starting unloading assembly from at least one candidate fuel assembly; wherein the at least one candidate fuel assembly is at least one fuel assembly arranged in the starting unloading direction; Starting from the initial unloading assembly, each of the fuel assemblies is unloaded in sequence according to a first preset route.

2. The method according to claim 1, characterized in that Starting from the starting unloading assembly, unloading each of the fuel assemblies in sequence according to a first preset route includes: Starting from the initial unloading assembly, unloading each fuel assembly in the nuclear power plant unit according to a first preset route; After the unloading of each fuel assembly is completed, for any neutron source assembly in the nuclear power plant unit, the neutron source assembly is switched from the corresponding initial position to the corresponding first target position.

3. The method according to claim 2, characterized in that The first target position corresponding to the neutron source assembly is determined based on the following method: Obtaining a switching reference angle of the nuclear power plant unit; Determining a first offset distance according to the switching reference angle and a core reference radius of the nuclear power plant unit; A first target position corresponding to the neutron source assembly is determined according to the first offset distance and an initial position of the neutron source assembly.

4. The method according to claim 1, characterized in that: The method further comprises: Determining the temporary placement position of each neutron source assembly in the nuclear power plant unit according to the setting position of the source range detector in the nuclear power plant unit; Placing each neutron source assembly in the nuclear power plant unit at a corresponding temporary placement position; Starting from a preset starting loading assembly, the fuel assemblies in the nuclear power plant unit are loaded sequentially according to a second preset route.

5. The method according to claim 4, characterized in that The method further comprises: After the loading of each fuel assembly is completed, for any neutron source assembly, the neutron source assembly is switched from the corresponding temporary placement position to the corresponding second target position.

6. The method according to claim 5, characterized in that The second target position corresponding to the neutron source assembly is determined based on the following method: Obtaining a switching reference angle of the nuclear power plant unit; Determining a second offset distance according to the switching reference angle and a core reference radius of the nuclear power plant unit; A second target position corresponding to the neutron source assembly is determined according to the second offset distance and the temporary placement position of the neutron source assembly.

7. A refueling device for a nuclear power plant unit, characterized in that: The device comprises: A first determination module is used to determine the starting unloading direction according to the setting position of the fuel transfer device in the nuclear power plant unit; wherein at least one fuel assembly is set in the core of the nuclear power plant unit; A selection module, used to select a starting unloading assembly from at least one candidate fuel assembly; wherein the at least one candidate fuel assembly is at least one fuel assembly arranged in the starting unloading direction; The unloading module is used to unload each of the fuel assemblies in sequence according to a first preset route starting from the starting unloading assembly.

8. A computer device comprising a memory and a processor, wherein the memory stores a computer program, wherein: When the processor executes the computer program, the steps of the method according to any one of claims 1 to 6 are implemented.

9. A computer-readable storage medium having a computer program stored thereon, characterized in that: When the computer program is executed by a processor, the steps of the method according to any one of claims 1 to 6 are implemented.

10. A computer program product, comprising a computer program, characterized in that When the computer program is executed by a processor, the steps of the method according to any one of claims 1 to 6 are implemented.

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